Irradiation Effects on Structural Alloys for Nuclear Reactor Applications

    Bement AL

    Pages: 570

    Published: 1970

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    The Symposium on Irradiation Effects on Structural Alloys for Nuclear Reactor Applications was presented at Niagara Falls, Canada, 29 June-1 July 1970, in conjunction with the Seventy-third Annual Meeting of the American Society for Testing and Materials held in Toronto, Ontario, Canada, 22-26 June 1970. The symposium was sponsored by ASTM Committee E10 on Radiosotopes and Radiation Effects. A. L. Bement, Jr., Battelle Memorial Institute, Pacific Northwest Laboratory, served as chairman of the symposium committee, which consisted of J. Moteff, cochairman, and K. M. Zwilsky, C. J. Baroch, E. Landerman, and L. E. Steele. The six sessions were presided over by L. J. Chockie, D. R. Harries, W. R. Thomas, R. Bullough, J. Moteff, and H. Bohm. Two agenda discussion sessions also were presented to survey the status of two contemporary problem areas.

    Table of Contents

    Bement A.
















    How Do We Solve the Void Problem?





    Neutron Dosimetry for Reactor Pressure Vessel Applications
    Morgan W., Serpan C.

    Radiation Effects on the Metallurgical Fracture Parameters and Fracture Toughness of Pressure Vessel Steels
    Ireland D., Tetelman A., Wullaert R.

    The Effect of Hydrogen on the Ductile Properties of Irradiated Pressure Vessel Steels
    Beeston J., Brinkman C.

    Evaluation of the Embrittlement of Pressure Vessel Steels Irradiated in JPDR
    Fujimura T., Kawasaki M., Namatame H., Suzuki K.

    Demonstration of Improved Radiation Embrittlement Resistance of A533B Steel Through Control of Selected Residual Elements
    Hawthorne J.

    Neutron Irradiation Effects on Iron Containing Aluminum and Nitrogen
    Hasiguti R., Igata N., Nishiike U., Watanabe K., Yagi E.

    The Effect of Fast Neutron Irradiation on the Mechanical Properties of Some Quenched and Tempered Steels
    Hosbons R., Wotton B.

    Structure and Composition Effects on Irradiation Sensitivity of Pressure Vessel Steels
    Steele L.

    Effects of Irradiation in a Thermal Reactor on the Tensile Properties of Zircaloy 2 and 4 and Borated Stainless Steel
    Baroch C., Harbinson E., Munim A.

    Influence of Irradiation Temperature on the Tensile Properties of Stainless Steel
    Bauer A., Kangilaski M., Spretnak J., Wullaert R.

    The Effect of Neutron Irradiation on the Mechanical Properties of Zirconium Alloy Fuel Cladding in Uniaxial and Biaxial Tests
    Hardy D.

    Metallurgical Properties of Cold-Worked Zircaloy 2 Pressure Tubes Irradiated Under CANDU-PHW Power Reactor Conditions
    Langford W.

    The Temperature and Neutron Dose Dependence of Irradiation Growth in Zircaloy 2
    Harbottle J.

    Quantitative Transmission Electron Microscopy of Bubbles in A1 and A1-A12O3 Alloys
    Ruedl E.

    The Mechanism and Kinetics of Void Growth During Neutron Irradiation
    Bullough R., Perrin R.

    Void Formation in Proton Irradiated Stainless Steel
    Keefer D., Kramer D., Neely H., Pard A., Robinson J.

    Considerations of Metal Swelling and Related Phenomena Caused by Fast Neutron Irradiation
    Franklin D., Harkness S., Li C.

    Some Observations on the Structure and Tensile Properties of AISI Type 316 Steel as a Function of Fast Reactor Irradiation Temperature
    Barton P., Higgins P.

    Neutron Dosimetry for Fast Reactor Applications
    Dahl R., McElroy W.

    Neutron Fluence Limit Determinations for Some Fast Flux Test Facility Components
    Moen R., Thomas K., Tobin J.

    Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures
    Beeston J., Brinkman C.

    Effect of Fast Neutron Irradiation on the Creep Rupture Properties of Type 304 Stainless Steel at 600 C
    Bloom E., Stiegler J.

    Uniaxial and Biaxial Creep Rupture of Type 316 Stainless Steel After Fast Reactor Irradiation
    Barker R., Lovell A.

    Effect of Irradiation on the Mechanical Properties of 19-9DL Alloy
    Baroch C., Lowe A.

    Influence of Neutron Irradiation on the Creep Rupture Properties of a 16Cr-13Ni Steel
    Böhm H., Ehrlich K., Wassilew C.

    The Effects of Helium on the High-Temperature Ductility of Sandvik 12R72HV and Inco IN-744X
    Garr K., Kramer D., Pard A., Rhodes C.

    Correlation Between the Mechanical Properties and Microstructure of Irradiated Iron and Low-Carbon Steel
    Milašin N., Stefanović V.

    Irradiation Effects at Cryogenic Temperature on Tensile Properties of Titanium and Titanium-Base Alloys
    Haley F., Younger C.

    Committee: E10

    Paper ID: STP484-EB

    DOI: 10.1520/STP484-EB

    ISBN-EB: 978-0-8031-4593-1

    ISBN-PRINT: 978-0-8031-0014-5

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